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Ganendra: Majalah IPTEK Nuklir
ISSN : 14106957     EISSN : 25035029     DOI : https://doi.org/10.17146/gnd
Core Subject : Science, Education,
Jurnal Iptek Nuklir Ganendra merupakan jurnal ilmiah hasil litbang dalam bidang iptek nuklir, diterbitkan oleh Pusat Teknologi Akselerator dan Proses Bahan (PTAPB) - BATAN Yogyakarta. Frekuensi terbit dua kali setahun setiap bulan Januari dan Juli.
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Articles 236 Documents
KAJIAN OPTIMALISASI PENGURANGAN TITIK SAMPLING RADIOAKTIVITAS LINGKUNGAN DI SEKITAR KAWASAN NUKLIR YOGYAKARTA Jasmi Budi Utami; Siswanti Siswanti; Eko Lestariningsih
GANENDRA Majalah IPTEK Nuklir Volume 24 Nomor 2 Juli 2021
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Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/gnd.2021.24.2.6299

Abstract

KAJIAN PENGURANGAN TITIK SAMPLING RADIOAKTIVITAS LINGKUNGAN DI SEKITAR KAWASAN NUKLIR YOGYAKARTA. Telah dilakukan kajian pengurangan titik sampling radioaktivitas lingkungan di sekitar Kawasan Nuklir Yogyakarta (KNY).  Berdasarkan pertimbangan pemantauan lingkungan di sekitar reaktor Kartini sampai dengan radius 5 km adalah berlebihan maka kajian pengurangan titik sampling perlu dilakukan. Tujuan dari kajian ini adalah untuk menentukan kemungkinan pengurangan titik lokasi sampling parameter pengawasan lingkungan antara lain: air, tanah dan tanaman di lingkungan sekitar KNY. Kajian pengurangan titik sampling didasarkan pada arah angin dominan dan evaluasi data pengukuran. Data dari Stasiun Meteorologi Adi Sucipto, Yogyakarta digunakan dalam penentuan arah angin dominan dan diolah menggunakan software WRPlot.  Evaluasi data dilakukan dengan menguji perbedaan antara rerata hasil pemantauan pada semua lokasi sampling dan rerata hasil pemantauan pada beberapa lokasi sampling. Evaluasi data dilakukan secara statistik menggunakan software PSPP versi 3. Hasil uji beda t antara data radioaktivitas air, tanah dan tanaman pada radius 100 - 1500 m dan data radioaktivitas air, tanah dan tanaman pada seluruh lokasi sampling, masing-masing diperoleh Sig=0,423; Sig=0,764; Sig=0,738; hal ini berarti rerata data tidak berbeda nyata. Selain uji beda t pada parameter tersebut juga dilakukan uji beda t pada data laju dosis radiasi lingkungan, diperoleh hasil Sig=0,81 yang berarti rerata data tidak berbeda nyata. Berdasarkan hasil kajian ini, dapat direkomendasikan bahwa lokasi sampling radioaktivitas lingkungan dilakukan cukup pada radius 100 - 1500 m dari pusat reaktor.
PRELIMINARY STUDY ON MINOR ACTINIDE INCINERATION IN RSG-GAS WITHOUT ISOTOPE SEPARATION R. Andika Putra Dwijayanto; Muhammad Alfarisie
GANENDRA Majalah IPTEK Nuklir Volume 24 Nomor 2 Juli 2021
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Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/gnd.2021.24.2.6241

Abstract

Minor actinides (MA) resulted from nuclear power plants is often considered as nuisance in spent fuel management due to its considerably long half-life. One of available strategies to deal with MA is to incinerate it, in order to reduce its radioactivity. This paper presents a study on MA incineration in RSG-GAS research reactor. Unlike previous study, this work did not separate the MA into individual isotopes, but incinerated as a whole. ORIGEN2.1 code is employed to calculate MA incineration within RSG-GAS core. MA composition used in this study consists of Np, Am, and Cm isotopes. The Central Irradiation Position (CIP) of RSG-GAS is loaded by 6 kg of MA and irradiated for two years. The result shows that about 1 kg of MA were incinerated after two years of irradiation, or 18,87% of the initial concentration. However, the increase of Cm-242 isotope, along with newly-formed Pu isotopes, were found to be significantly increasing short-term radioactivity compared to un-irradiated MA. Thus, two years-worth of MA incineration cannot be considered as effective, and other strategies must be pursued.
PLANAR SCINTIGRAPHY IMAGE DE-NOISING USING COIFLET WAVELET Ayu Jati Puspitasari; Ika Cismila Ningsih; Muhammad Sulthonur Ridwan; Halim Hamadi
GANENDRA Majalah IPTEK Nuklir Volume 24 Nomor 2 Juli 2021
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Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/gnd.2021.24.2.6280

Abstract

The planar scintigraphic image usually has poor resolution and contains noise. This noise can be removed using the coiflet wavelet method so that the image quality gets better. This coiflet wavelet method is a noise reduction method based on frequency analysis. The planar scintigraphy image is the reconstructed image of the gamma radiation count data (phantom with the Cs-137 source in it). The original image is 15×15 pixel. Before the de-noising process, the image went through an interpolation process, which is to increase the pixel size of the image. The original image enlarged to 70×70, 480×480, and 1200×1200 pixel. After de-noising with coiflet wavelet, the image quality is measured based on MSE and PSNR parameters. The resulting images are quite good, with MSE values are close to zero and PSNR values of more than 60 dB. The smaller the MSE and the bigger the PSNR, is getting the better the image quality. In this study, the results show that the 1200×1200 pixel image has the best quality. It means that the image enlargement process has a good effect on the de-noising process, especially if the original image has a low resolution.
EFFECT OF COLLIMATOR ELEMENTS ON THE BEAM SPECTRUM AND KERMA IN GAMMA IRRADIATOR Rasito Tursinah; Bunawas Bunawas; Tri Cahyo; Ade Suherman; P Sukmabuana
GANENDRA Majalah IPTEK Nuklir Volume 24 Nomor 2 Juli 2021
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Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/gnd.2021.24.2.6307

Abstract

In the development of low-medium energy photon calibration facilities we have simulated several types of gamma irradiator collimator materials with ISO 4037-1 design connected to the output beam spectrum and the resulting kerma. Four types of collimator material, namely Al, Fe, Pb, and WCu have been simulated with gamma radiation sources 241Am, 57Co, 137Cs, and 60Co. Simulations were carried out using the Monte Carlo method with the PHITS computer program. Based on the comparison of air kerma produced, collimators made from Al are suitable for gamma sources 241Am, Fe material for gamma sources 57Co, and Pb material for sources 137Cs and 60Co.
AN ANALYSIS OF CYLINDRICAL BORIS SOLVER FOR TYPICAL PARAMETERS OF TWO-DIMENSIONAL PENNING ION SOURCE SIMULATION Shali, Ahsani Hafizhu; As'ari, Ahmad Hasan
GANENDRA Majalah IPTEK Nuklir Volume 26 Nomor 2, 2023
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Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/gnd.2023.6791

Abstract

The cylindrical Boris solver is analyzed for typical two-dimensional Penning ion source simulation parameters. The analysis comprises the solver's accuracy and stability, especially for the latter simulation stages, typically after about 30 μs. The simulation is done for two cases; the first is a gyration simulation with a homogenous magnetic field, and the second uses the same setup as the Penning simulation. Several investigated quantities to determine the error are the radial position, axial position, and velocity magnitude (or kinetic energy). The error is calculated by comparing the result with the reference result from the exact solver with an incredibly small time step width, dt = 10-15  s. The result shows a discrepancy between cylindrical and cartesian Boris solvers. The velocity magnitude of the particle decays as time goes on for the cylindrical Boris solver, especially when the particle is close to the z-axis, an error not found on the cartesian solver. For typical Penning simulation parameters, the trajectory of individual particles is way off the reference trajectory. However, the mean position is relatively close to the reference compared to the dimension of the simulation domain. The kinetic energy is also relatively accurate, with a similar slow decay related to the deteriorating non-axial velocity components previously observed in the first case. Thus, for the simultaneous simulation of millions of particles, there should not be any significant observable difference in actual Penning simulation compared to Penning simulation with reference time step width.
Analisis Tingkat Absorbsi Berkas Sinar-X Pada Sintesis Komposit Kaktus (Opuntia Spp.) dan Timbal (II) Asetat (Pb(CH3COO)2) Sebagai Material Apron Rahmawati, Intan; Jumpeno, B.Y. Eko Budi; Mellawati, June; Ramlan, Ramlan
GANENDRA Majalah IPTEK Nuklir Volume 26 Nomor 2, 2023
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Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/gnd.2023.6870

Abstract

Apron proteksi radiasi efektif dalam mengurangi paparan laju dosis radiasi sinar-X, namun sebagai baju pelindung radiasi masih memiliki kelemahan, diantaranya relatif berat (5 - 7 kg) sehingga akan berdampak buruk pada sistem musculoskeletal tubuh terutama pada posisi tulang belakang. Tujuan penelitian untuk memperoleh sintesis komposit material apron proteksi radiasi yang dapat menyerap radiasi sinar-X secara optimal dan nyaman digunakan. Penelitian ini menggunakan bahan serat kaktus Opuntia ficus-indica ukuran 80 mesh, disintesis dengan timbal (II) asetat sebagai bahan pengisi dengan variasi 20, 33, 50, 67, dan 80% sehingga diperoleh tebal komposit berkisar 0,36 - 0,74 cm. Pengujian menggunakan rontgen radiografi umum dan alat ukur radiasi Unfors RaySafe XI dengan energi 80 kVp, arus 50 mA, serta jarak antara tabung sinar-X dengan detektor sejauh 100 cm. Hasil penelitian menunjukkan bahwa makin banyak komposisi serat kaktus pada sampel, makin kecil nilai koefisien atenuasi yang diperoleh. Koefisien atenuasi maksimum adalah 3,85 cm-1 diperoleh pada variasi timbal (II) asetat 80% dengan tebal 0,41 cm dan berat RAR 84%. Pada variasi 80% tersebut diperoleh densitas paling optimal, koefisien atenuasi, dan RAR paling tinggi, serta HVL paling rendah.
STUDY OF POISSON NOISE REDUCTION ON GAMMA CAMERA IMAGE USING SPATIAL DOMAIN FILTER Puspitasari, Ayu Jati; Karthika, Risky Nurseila; Nugrahani, Puspa Ayu; Febrianti, Widya; Hidayati, Nur Rahmah
GANENDRA Majalah IPTEK Nuklir Volume 26 Nomor 1, 2023
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Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/gnd.2023.6822

Abstract

A gamma camera image is produced by a gamma camera that detects the gamma radiation emitted by the radioactive substance or radiopharmaceutical injected into the body. The gamma camera image sometimes has noise that can interfere with the diagnosis. This image is commonly affected by a Poisson-type random noise. This research proposes using a spatial domain filter to study Poisson noise reduction in gamma camera images. The image sample used is the image of a mouse injected with Lu-177-DOTA Trastuzumab with 100 µCi activity detected using a dual-head gamma camera with NaI(Tl) detectors. The grayscale image is treated with Poisson noise, then improved using a spatial domain filter. The spatial domain filters used include Mean, Median, Wiener, and Spatial Lowpass Filters. The mean filter is the best one that can reduce Poisson noise among the four applied filters. The best filter size for noise reduction is 3 with MSE 5.07, PSNR 41.08 dB, and SSIM 0.99.
ARDUINO AND IOT-BASED OBSERVATION METHOD FOR MONITORING TEMPERATURE, HUMIDITY, AND AIR PRESSURE OF ELECTRON BEAM ACCELERATOR’S ROOM Rachmawati, Isti Dian; Linandia, Ismi Putri Mei; Fajarudin, Rizky; Saefurrochman, Saefurrochman; Adabiah, Suhadah Rabi'atul
GANENDRA Majalah IPTEK Nuklir Volume 26 Nomor 2, 2023
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Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/gnd.2023.6842

Abstract

The monitoring system for temperature, humidity and air pressure in the electron accelerator’s room has been designed. This research is based on operational environmental monitoring procedures in the accelerator room that must be carried out before the accelerator operates. We offer a simple and adaptable monitoring solution for the electron accelerator room. Parameter data can be monitored using a smart device. Operators do not need to go into the accelerator room to carry out environmental monitoring. The proposed system uses Arduino technology and the Internet of Things (IoT). Data acquisition programming was performed using Arduino IDE and ESP8266 NodeMCU as microcontrollers. The microcontroller then transmits temperature, humidity, and pressure data parameters to the cloud server, where they are then displayed on the smart device via the Blynk app. The results show that the system that has been designed is able to read and store parameter readings on the sensors used and the system has been able to make decisions in the form of notifications about whether the Electron Beam Machine is ready or not to be operated.
PENENTUAN TINGKAT KLIERENS LIMBAH RADIOAKTIF HASIL SEMENTASI KONSENTRAT EVAPORASI DAN TINJAUAN KESELAMATAN PEMBUANGANNYA Suhartono, Suhartono; Kundari, Noor Anis; Romli, Moch.; Sumarbagiono, Sumarbagiono
GANENDRA Majalah IPTEK Nuklir Volume 26 Nomor 1, 2023
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Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/gnd.2023.6839

Abstract

Telah dilakukan penelitian untuk mengukur tingkat klierens 14 unit shell beton 950 L milik Instalasi Pengelolaan Limbah Radioaktif, Direktorat Pengelolaan Fasilitas Ketenaganukliran, Badan Riset dan Inovasi Nasional (IPLR-DPFK BRIN). Shell-shell beton tersebut merupakan paket hasil olahan konsentrat evaporasi limbah radioaktif cair yang dikondisioning dengan teknik sementasi. Jika telah memenuhi tingkat klierens, maka shell-shell beton tersebut dapat dibebaskan dari pengawasan Badan Pengawas Tenaga Nuklir (BAPETEN) melalui mekanisme klierens sehingga pada akhirnya dapat menambah ruang kosong di gedung penyimpanan sementara limbah radioaktif. Penelitian dilakukan dengan mengukur laju dosis radiasi, tingkat kontaminasi permukaan, dan konsentrasi aktivitas radionuklida pemancar α, β, dan ϒ untuk menentukan tingkat klierens. Dari penelitian yang telah dilakukan dapat diketahui bahwa laju dosis tertinggi 0,15 µSv/jam, tingkat kontaminasi permukaan tertinggi sebesar 0,0148 Bq/cm2 untuk radionuklida pemancar α dan 0,0935 Bq/cm2 untuk radionuklida pemancar β. Nilai tingkat klierens radioaktivitas unit shell beton 950 L yang diuji berkisar antara 0,47020 – 0,66730. Mengacu pada Peraturan Kepala BAPETEN Nomor 16/2012 tentang Tingkat Klierens, kandungan radionuklida dalam shell-shell beton 950 L yang diuji telah mencapai tingkat klierens. Pembuangan klierens terhadap 14 unit shell beton tersebut sangat mungkin untuk dilakukan karena shell-shell beton tersebut tidak mengandung bahan berbahaya dan beracun (B3). Perkiraan dosis radiasi yang akan diterima oleh kelompok kritis, tidak akan melebihi 10 µSv per tahun.     
SINTESIS PADUAN BARU BAJA OXIDE DISPERSION STRENGTHENED (ODS) FERITIK Fe-Cr-Al-W-Ti-Zr DENGAN DISPERSOID Y2O3 SEBAGAI KANDIDAT MATERIAL CLADDING ELEMEN BAKAR REAKTOR NUKLIR DENGAN METODE MEKANOSINTESIS Wafda, Hakimul; Prajitno, Djoko Hadi; Mustari, Asrili Pramutadi Andi; Roswita, Fahma
GANENDRA Majalah IPTEK Nuklir Volume 26 Nomor 2, 2023
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Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/gnd.2023.6856

Abstract

Bahan struktur merupakan salah satu kunci penting dalam penelitian reaktor nuklir generasi keempat. Sejak peristiwa kecelakaan di pembangkit listrik tenaga nuklir Fukushima–Daiichi, telah terjadi peningkatan pengembangan Accident Tolerant Fuel (ATF) Cladding atau kelongsong bahan bakar toleran kecelakaan untuk menghindari kecelakaan reaktor air ringan. Maka dari itu Inovasi perekayasaan ATF merupakan salah satu kegiatan dalam litbang material maju yang sedang banyak dikembangkan. Kandidat material yang paling menjanjikan untuk ATF cladding adalah Baja yang diperkuat dengan dispersi oksida (ODS). Dalam penelitian ini baja ODS feritik Fe-Cr-Al-W-Ti-Zr-Y2O3 disintesis dengan metode mekanosintesis menggunakan alat planetary ball mill (PBM) dengan variasi komposisi Zr sebesar 0%, 0.5%, 1%, dan 1.5%. Mekanosintesis dilakukan selama 8 jam dengan menggunakan bola stainless steel. Perbandingan berat antara sampel dengan bola adalah 1:10. Kemudian dilakukan karakterisasi menggunakan mikroskop optik, XRD, dan SEM-EDS. Hasil observasi menunjukkan homogenitas yang baik pada bahan hasil sintesis.